ML20236M694
| ML20236M694 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/05/1987 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236M698 | List: |
| References | |
| NUDOCS 8708110188 | |
| Download: ML20236M694 (13) | |
Text
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UNITED STATES
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)o NUCLEAR REGULATORY COMMISSION 5
E WASHtNGTON, D. C, 205S5 t
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BOSTON EDISON COMPANY 1
I DOCKET NO. 50-293 i
PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. DPR-35 j
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1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Boston Edison Company (the licensee) dated May 29, 1987 as supplemented by a letter dated July 15, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act)..and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:
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KO O P
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.102, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately.
[
FOR THE NUCLEAR REGULATORY COMMISSION h
Victcr Perres, Acting Directcr Project Directorate I-3 Division of Reactor Projects I/II l
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 5, 1987
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ATTACHMENT TO LICENSE AMENDMENT NO. 102 i
FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical Specifications t";h the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.- The corresponding overleaf pages are provided to maintain document completeness.
Remove Pages Insert Pages 95 95 96 96 97 97 97a*
98 98 i
95 99**
100 100 1
101 101 102 102**
i 2?5 225
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3,4 STANDBY LIOUID CONTROL SYSTEH 4.4 STANDBY LIOUID CONTROL SYSTEM Aeolicability:
'Anolicability:
Applies to the operating status Applies to the surveillance of the Standby Liquid Control requirements of the Standby System.
Liquid Control System.
Obiettive:
Obiective:
To assure the availability of a To verify the operability of the system with the capability to Standby Liquid Control System, shutdown the reactor and maintain the shutdown condition without the use of control rods.
Specification:
Specification:
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A.
Normal System Availability
'A'. Normal System Availability i
1.
During periods when fuel is The operability of the Standby in the reactor and prior to Liquid Control System sha.11 be' startup from a cold verified by the performance of condition, the Standby Liquid the following tests:
Control System shall be operable, except as specified 1.
At least once per month in 3.4.B below. This system each pump loop shall be j
6 need not be operable when the functionally tested by reactor is in the Cold recirculating Shutdown Condition, all demineralized water to the operable control rods are test tank.
fully inserted and Specification 3.3.A is set.
2.
At least once during each operating cycle:
a.
Check that the system relief valves trip full open'at pressures less than 1800 psig, and reseat on a falling pressure greater _than 1275 psig.
b.
Manually initiate the-system, except-explosive valves.
Pump boron solution
.through the recirculation path and back to the Standby Liquid Control Solution Tank. Check that each pump flow rate meets or exceeds 39 GPM against a system head of 1275 psig.
Amendnent No. 102 95
4 LIMITING _fDN2]TIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIOUID CONTROL SYSTEM
'4.4 STANDBY L10UID CONTROL SYSTEM c.
Manually initiate one of the Standby Liquid Control System-loops and pump demineralized water into the reactor vessel.
This test checks explosion of the charge associated with the tested loop, proper operation of the valves, and pump operability. The replacement charges'to be installed will be selected from the same manufactured batch as the tested charge.
d.
Both systems, including both explosive valves, shall be tested in the course of two operating cycles.
B.
Oceration with Inocerable B. Surveillance with Inonerable Comoonents:
Comoonen2s:
1.
From and after the date 1.
When a component is found that a redundant to be inoperable, its component is made or redundant component shall found to be inopera'ble, be demonstrated to be Specification 3.4.A.1 operable immediately and shall be considered daily thereafter until the fulfilled and continued inoperable component is operation permitted repaired.
provided that the component is returned to an operable condition within seven days.
1 Amendment No. 102 96 1
i LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS I
3.4 STAND 5Y LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM C.
Sodiur Pentaborate Solution C. Sodium Pentaborate Solution At all times when the Standby The following tests shall be l
Licuid Control System is performed to verify the recuirec to be operable the availability of the Liquid following conditions shall be Control Solution:
met:
1.
Volume:
Check at least 1.
The net volume -
once per day.
concentration of the Liauid Control Solution 2.
Temperature:
Check at in the liquid control least once per day, tank shall be maintained as reauired in Figure 3.
Concentration:
Check at 3.4-l.
least once per month.
Also check concentration 2.
The temperature of the anytime water or boron is liquid control solution added to the solution, or shall be maintained above the solution temperature 48*F.
If the solution is at or below 48'F.
temperature falls to or i
below 48*F, the system 4.
Enrichment: Check B' I
will be flow tested to enrichment level by test verify aflow path.
anytime boron is added to the solution and during 3.
The enrichment of the each refueling outage.
liquid control solution Enrichment analyses shall shall be maintained at a be received within 30 days l
S
isotope enrichment of test performance.
If exceeding 54.5 atom not received within 30 percent.
days, see Table 6.9.1 for reporting requirements.
D.
There are two operational considerations associated with the Standby Liquid Control sodium pentaborate solution requirements.
The first consideration involves sodium pentaborate concentration / volume requirements.
The second consideration involves B' isotopic enrichment. The related Limiting Conditions for Operation are delineated below:
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AmendmentNo. 102 97 Wh m+a wde--
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'3.4 STAND 8Y CONDIT' IONS FOR OPERATION SURVEILLANCE RE0VfREMENTS 3.4 STANDBY LIOUID-CONTROL SYSTEM 4.4 STANDBY ~LIOUID CONTROL SYSTEM'
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. 1 D.l.If specification 3.4.A..B, or C.1 or C.2~cannot.be met, the reactor shall be placed.in.a Cold Shutdown Condition with i
all operable control rods ful.ly inserted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
'D.2 If the enrichment requirements of specification q
3.4.C.3 are.not met, a check q
shall be made to ensure that
.]
i
-sodium-pentaborate solution meets the original design f
criteria by comparing the enrichment, concentration and 3
I volume to established i
criteria.
If the sodium pentaborate solution does not meet the original design criteria. the reactor shall be placed in a Ccid Shutdown l
Condition with all operable control. rods fully inserted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I D.3 If the sodium pentaborate l
solution meets the original design criteria, but the enrichment requirements of specification 3.4.C.3 are not met, bring the B' isotopic i
i enrichment to greater than 54.5 atom percent within seven days from the time of receipt of the enrichment.
report. If after this time period the enrichment 1
requirements of specification 1
3.4.C.3 are still not met, 1
submit a report to the NRC
. j within seven days and advise i
them of plans to bring the i
l solution.up to a l
demonstratable 54.5 atom percent 8' isotopic enrichment.
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. Amendment flo.102 97a
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j Page 99 I
(intentionally deleted) i
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I Amendment No. 102 99
i BASES:
3.4 & 4.4 STANDBY LIOUID CONTROL SYSTEM A.
The requirements for SLC capability to shut down the reactor-are identified via the station Nuclear Safety Operational Analysis (Appendix G to the FSAR, Special Event 45).
If no more than one operable control rod is withdrawn, the basic shutdown reactivity requirement for the core.is satisfied and i
the Standby Liquid Control system is not required.
Thus, the j
basic reactivity requirement for the core is the primary l
j I
determinant of when the standby liquid control system is.
required. The design objective of-the standby liquid control system is to provide the capability of bringing the reactor from full power to a cold, xenon-free shutdown condition assuming that none of the withdrawn control rods'can be inserted.
To meet this objective, the Standby Liquid Control system is designed to inject a quantity of boron that produces a concentration equivalent to 700 ppm of natural boron in the i
l reactor core.
The 700 ppm equivalent concentration in the
.j reactor core is required to bring the reactor from full' power to a three percent 4 k Subtritical condition, considering the l
hot to Cold reactivity difference, xeaon poisoning etc.
The system will inject this boron solution.in less than 125 j
minutes. The maximum time requirement for inserting the boron solution was selected to override the rate of reactivity insertion caused by cooldown of the reactor following the xenon poison peak.
The Standby Liquid Control system is also required to meet 10CFR50.62 (Requirements for Reduction of Risk from Anticipated Transients Without Scram (ATWS) Events for Light-Water-Cooled Nuclear Power Plants).
The Standby Liquid Control system must have the equivalent control capacity (injection rate) of 86 gpm at 13 percent by wt. natural sodium pentaborate for a 251" diameter reactor pressure vessel in order to satisfy 10CFR50.62 requirements.
This corresponds to an equivalent control, capacity (injection rate) of 66'gpm at 13 percent by wt.
natural sodium pentaborate solution for the PNPS reactor pressure vessel diameter of 218".
This equivalency requirement is fulfilled by a combination of concentration, B' enrichment i
and flow rate of sodium pentaborate solution. A minimum 8.42%
concentration and 54.5% er.richment of B' isotope at a 39 GPM pump flow rate satisfies the ATWS Rule (10CFR 50.62) equivalency requirement.
Because the concentration / volume curve has been revised.to reflect the increased B isotopic enrichment,'an additional requirement has been added to evaluate the solution's l
capability to meet the original design shutdown criteria 4
whenever the B enrichment requirement is not met.
Experience with pump operability in.iicates that the monthly
)
test, in combination with the tests during each operating cycle, is sufficient to maintain pump performance.
The only practical time to fully test the liquid control system is during a refueling outage. Various components of the' system are individually tested periodically, thus' making more frequent testing of the entire system unnecessary.
]
j
, Amendment No. 102 100 1
SASES:
3.4 & 4.4 STANDBY LIOUID CONTROL SYSTEM (Cont'd) l The minimum limitation on the relief valve setting is intended to prevent the loss of sodium pentaborate solution via the lifting of a relief valve at too low a pressure.
The upper limit on the relief vhive settings provides system protection from overpressure.
B.
Only one of the two standby liquid control pumping loops is needed for operating the system. One inoperable pumping circuit does not immediately threaten the shutdown capability, and reactor operation can continue while the circuit is being repaired. Assurance that the remaining system will perform its intended function and that the long term average availability of the system is not reduced is obtained for a one out of two j
system by an allowable equipment out of service time of one l
third of the normal surveillance frequency.
This method aete nines an equicment out of service time of ten days.
l Additional conservatism is introduced by reducing the allowable i
out of service time to seven days, and by increased testing of the operable redundant component.
i C.
'he quantity of B' stored in the Standby Liquid Control System l
Storage Tank is sufficient to bring the concentration of B' in
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the reactor to the point where tM reactor will be shutdown and I
(
to provide a minimum 25 parcent margin beyond the amount needed I
to shutdown the reactor to allow for possible imperfect mixing l
of the chemical solution in the reactor water, j
l Level indication and alarm indicate whether the solution volume j
i I
has changed, which might indicate a possible solution concentration change.
Test intervals for level monitoring have been established in consideration of these factors.
Temperature and liquid level alarms for the system are i
annunciated in the control room.
i i
The solution shall be kept at least 10*F above the maximum saturation temperature to guard against boron precipitation.
Minimum solution temperature is 48'F.
This is 10*F above the saturation teniperature for the maximum allowed sodium pentaborate concentration of 9.22 Wt. Percent.
Each parameter (concentration, pump flow rate, and enrichment) is tested at an interval consistent with the potential for that parameter to vary and also to assure proper equipment performance.
Enrichment testing is required when material is received and when chemical addition occurs since change cannot occur by any process other than the addition of new chemicals to the Standby Liquid Control solution tank.
101 Amendment No. 10p
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Page 102 (intentionally deleted) i l
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' Amendment l10. ' 102
_ -. J 102
-TABLE 6.9.1 Area Reference Submittal Date I
a.
Se:ondary Containment 4.74C.c Upon completios of' l
Leak Rate Testing (1).
each test (2) y l
4 l
b.
(Deleted)
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l c.
(Deleted) l l'
i d.
Gross Gaseous Release 4.8.B.
Ten days after the 0.05 Ci/sec for 48 release occurs i
Hours e.
Standby Liquid Control 3.4.C.3 Fourteen days after l
solution enrichment out receipt of a non-of specification complying enrichment t
l report or lack of receipt of such a report within the. required
]
thirty days, if l
enrichment compliance
.cannot be achieved within seven days.
NOTES:
1.
Each integrated leak rate test of the secondary containment I
shall be the subject of a summary technical report.
This report shall include data on the wind speed, wind direction, outside and inside temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate.
The report shall also include analyses and interpretations of those data which demonstrate compliance with the specified leak rate
- limits, 2.
The report shall be submitted within 90 days after completion of each test. Test periods shall be based on the commerc'41 1
service data as the starting point.
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=
Amendment flo. 102 225 i
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